A conceptual project for a divertor monitor of the neutron yield in the ITER

The operating conditions of a neutron diagnostic system responsible for measuring the neutron yield in the ITER tokamak reactor are analyzed. Based on results of physical calculations and analysis of suitable methods for measuring the neutron yield, an original concept of a system for measuring neutron fluxed in the divertor zone of the ITER is proposed. The design for the neutron flux monitor located in the divertor zone of the tokamak is selected in view of the requirements specified for the neutron diagnostic system of the ITER and its operating conditions. Four fission chambers with different sensitivities and radiator materials are used as sensitive elements of the monitor. This system is capable of measuring neutron fluxes over the entire dynamic range of the neutron yield in the ITER with an error of ≤10% and a time resolution of 1 ms that are necessary for studying the physical mechanism of thermonuclear plasma ignition and burning. Several possible variants for housing the detector unit inside the divertor assembly and integrating it in the existing project are proposed. The problems of carrying out efficiency calibration of the divertor neutron monitor with the aim of determining the absolute value of the neutron yield in the ITER tokamak reactor are discussed.     

Operation Request Gatekeeper: a software system for remote access control of diagnostic instruments in fusion experiments

Tokamak diagnostic settings are repeatedly modified to meet the changing needs of each experiment. Enabling the remote diagnostic control has significant challenges due to security and efficiency requirements. The Operation Request Gatekeeper (ORG) is a software system that addresses the challenges of remotely but securely submitting modification requests. The ORG provides a framework for screening all the requests before they enter the secure machine zone and are executed by performing user authentication and authorization, grammar validation, and validity checks. A prototype ORG was developed for the ITER CODAC that satisfies their initial requirements for remote request submission and has been tested with remote control of the KSTAR Plasma Control System. This paper describes the software design principles and implementation of ORG as well as worldwide test results.     

The tri-band high-resolution spectrometer for the ITER CXRS diagnostic system

A tri-band high-resolution spectrometer, which was designed for performing diagnostics on the ITER facility using the charge-exchange recombination spectroscopy (CXRS), is described. The CXRS allows measurements of such plasma parameters as the ion temperature, the speed of the toroidal and poloidal plasma rotation, and the concentration of light impurities. The spectrometer is based on three transparent holographic diffraction gratings and is designed to operate simultaneously in three spectral bands: 468 ± 6 nm, 529 ± 6 nm, and 656 ± 8 nm. The results of measuring the main performance parameters of the transparent diffraction gratings and the spectrometer as a whole are presented. It was established that the characteristics of the developed spectrometer satisfy the requirements for the spectroscopic equipment for the ITER CXRS diagnostic system.     

基于吊丝悬架的地面微重力补偿实验系统设计

地面微重力补偿实验系统越来越多地应用于智能助力设备上。ITER装置内受损零件的更换由操作员通过遥操作机器人主机械手操控从机械手完成,为了使操作员操控省力,需要对主机械手进行重力补偿。基于吊丝悬架的微重力补偿方案,设计了一种吊丝摆角测量装置,能够方便有效地实现吊丝摆角的测量。首先对系统进行总体设计,然后对吊丝摆角测量装置进行理论计算及ADAMS运动学仿真,得出了该装置对吊丝摆角测量的放大倍数,接着设计了系统的控制方案,最后对系统进行相关补偿实验,验证了该设计的可行性。     

A comparative analysis of the sensitivity of CsI (Tl), ZnO(Ga), and YAG(Ce) scintillators to the plasma background radiation under operating conditions of the ITER tokamak reactor

Problems related to neutral particle flux measurements on the ITER tokamak reactor under intense plasma background radiation conditions are considered. The results of measuring a background sensitivity with respect to neutron and γ-radiation for the scintillation detector, which is based on three different crystals (CsI (Tl), ZnO(Ga), and YAG(Ce)), are presented. The scintillators are compared and conclusions about the possibility of their applications in detectors of neutral particle analyzers currently created at the Ioffe Institute for the ITER tokamak reactor, are drawn.     

Progress in the MITICA beam source design

In the framework of the development of the ITER neutral beam (NB) system, a test facility is planned to be built in Padova. A full size prototype of the ITER heating NB injector (MITICA) shall be built and tested at full beam power (17 MW) as per ITER requirements. The design of the MITICA beam source has further progressed following updated optimization and overall integration criteria. In the paper, the major design choices and revisions are presented, together with some results of numerical analyses carried out in order to assess the electrostatic and thermo-mechanical behaviour of the source.     

Carbon fiber composite targets for nuclear fusion technology: a focused ion beam/scanning electron microscope investigation

Carbon fiber composite (CFC) targets are investigated by a focused ion beam/scanning electron microscope (FIB/SEM) in a joint project aiming at the development of robust divertors in the International Thermonuclear Experimental Reactor (ITER). These mockups are exposed to a plasma that simulates the off-normal thermal loads foreseen for ITER and display a rich, puzzling impact scenario. Morphological elements are identified at the exposed surface and beneath it, and are examined in order to point out the relevant processes involved. Each technique adopted is discussed and evaluated.     

A method for monitoring the parameters of a stripping target in neutral particle analyzers for the ITER

A method is described, which will be used as a basis for designing a system for monitoring the parameters of a stripping target in neutral particle analyzers being developed for neutral particle diagnostics of the ITER plasma. This method is based on examining the target by a beam of alkali ions and measuring the energy spectrum of the beam passed through it. Results of testing of this method at the experimental facility—a model of the monitoring system—are presented. Based on analysis of the experimental data obtained in the study, conclusions are drawn on the applicability of this method to monitoring of the stripping target parameters.     

Development of novel fuel ion ratio diagnostic techniques

To overcome the challenge of measuring the fuel ion ratio in the core (ρ<0.3) of ITER, a coordinated effort aiming at developing diagnostic techniques has been initiated. The investigated techniques are novel uses or further development of existing methods such as charge exchange recombination spectrometry, neutron spectrometry, and collective Thomson scattering. An overview of the work on the three diagnostic techniques is presented.     

三峡大坝连续浇筑系统控制技术

介绍了三峡大坝混凝土连续浇筑系统的组成及其控制技术，重点叙述Profibus现场总线技术的应用，主站与上位监控系统的组成和通讯，以及计量输送机的运行、打滑检测和对位。     

Development of a Concept of Reflectometric Diagnostics for the ITER Tokamak for Plasma Probing from the High-Magnetic-Field Side

The capabilities of the reflectometric diagnostics in the ITER facility during plasma probing from the high-magnetic-field side are investigated. This technique allows measurements of the density profile and the plasma turbulence-rotation velocity at the lower extraordinary wave from a plasma with a critical density to the center of the plasma column. The system also allows one to probe the plasma column at the ordinary wave. It is proposed to use a combined mirror–horn antenna system. Under conditions where there is limited space for placing horns, this results in a significant (up to 20 dB) increase in the signal, compared to the system of two horns considered earlier. The results of calculations on optimizing the elements of the waveguide transmission line using a two-dimensional full-wave code are presented. The possibility of employing the Doppler effect to study plasma rotation by using antennas for controlling the shape of the plasma column while performing reflectometry at the lower extraordinary wave is considered. This effect is estimated theoretically in the actual ITER plasma configuration.     

Parametric study for conductor design of KSTAR PF coils

Large superconducting magnets such as ITER (International Thermonuclear Experimental Research) or KSTAR (Korean Superconducting Tokamak Advanced Research) magnet system adopted a cable-in-conduit conductor (CICC) using a forced-flow cooling system. Main optimization criteria for the conductor design of superconducting magnet system are stability margin and CICC cooling requirements. A zero-dimensional method is applied for the calculation of stability and the conductor optimization. In order to increase conductor performance, three different strands, ITER HP-I and HP-TI, and KSTAR HP-III, are tested. The strand characteristics of KSTAR HP-III are measured in the Samsung’s PPMS and Jc measurement system, and applied for this study. Also, the strand diameters, 0.81 mm and 0.78 mm are considered for this study, due to design change. Based on this result, the proposed configuration of CICC has been fabricated.     

The development of Campbell integration system applied in high particle flux measurement

Campbell Mode is a method widely used in nuclear signal processing. In this article, we introduce the design of the new system based on the Campbell integration measurement applied in NFM (neutron flux measurement) systems for ITER plasma diagnose. In this article, we introduce a digital particle flux measurement system based on Campbell integration theory. A subsequent series of experiment are conducted to test the digital Campbell system performance, which proves that the Campbell integration system is competent for the plasma diagnose in ITER.     

基于FPGA永磁同步直线电机性能检测系统的实现

结合永磁同步直线电机伺服控制技术研究项目,开发了永磁同步直线电机性能检测系统.利用编程逻辑器FPGA与硬件编程语言VHDL,实现通用异步收发器(UART)的设计,测试系统软件采用面向对象编程语言VB6.0中的MSCOMM通讯控件来产生通讯事件,实现对检测数据的传送与后处理.     

Effect of neutron irradiation on the electrodes of a vacuum photoemission detector

The effect of neutron irradiation on Ta-Be photocathodes of a vacuum photoemission detector (VPD) has been investigated. The VPD has been designed for tomography of plasmas using thermal X-ray radiation on the ITER international tokamak reactor. The exposure of VPD electrode samples to neutrons with a fluence of 1.6 × 10¹⁹ neutrons/cm² (E > 0.1 MeV) is shown to change the relative concentration of Ta and Be in the surface layer. As a result, the detector sensitivity in the DT operating mode of the ITER is inevitably altered. Some recommendations concerning selection of materials for the VPD electrodes are presented. The conclusion is drawn that sputtering by thermonuclear neutrons in the ITER may lead to deposition of a conductive film on the insulator surface and that a special shape of insulators must be therefore used to avoid formation of such a coating.     

Development of two-channel prototype ITER vacuum ultraviolet spectrometer with back-illuminated charge-coupled device and microchannel plate detectors

A vacuum ultraviolet (VUV) spectrometer of a five-channel spectral system is designed for ITER main plasma impurity measurement. To develop and verify the system design, a two-channel prototype system is fabricated with No. 3 (14.4-31.8 nm) and No. 4 (29.0-60.0 nm) among the five channels. The optical system consists of a collimating mirror to collect the light from source to slit, two holographic diffraction gratings with toroidal geometry, and two different electronic detectors. For the test of the prototype system, a hollow cathode lamp is used as a light source. To find the appropriate detector for ITER VUV system, two kinds of detectors of the back-illuminated charge-coupled device and the microchannel plate electron multiplier are tested, and their performance has been investigated.     

基于LabVIEW的高能液压马达性能试验测控系统

为了验证新型高能液压马达设计的预期性能,需要测试其在给定工作条件下的技术特性和参数。针对这一要求,设计了一种用于高能液压马达性能试验的测控系统。从液压系统、加载系统以及软硬件系统等方面详细介绍了测控系统的设计过程,重点阐述了基于LabVIEW平台的系统软件架构。同时,该测控系统采用了利用电液比例溢流技术来提高测控系统的静态和动态的加载性能。该测控系统已经投入使用,证明完全可以满足项目试验要求。     

Optimization studies of the ITER low field side reflectometer

Microwave reflectometry will be used on ITER to measure the electron density profile, density fluctuations due to MHD/turbulence, edge localized mode (ELM) density transients, and as an L-H transition monitor. The ITER low field side reflectometer system will measure both core and edge quantities using multiple antenna arrays spanning frequency ranges of 15-155 GHz for the O-mode system and 55-220 GHz for the X-mode system. Optimization studies using the GENRAY ray-tracing code have been done for edge and core measurements. The reflectometer launchers will utilize the HE11 mode launched from circular corrugated waveguide. The launched beams are assumed to be Gaussian with a beam waist diameter of 0.643 times the waveguide diameter. Optimum launcher size and placement are investigated by computing the antenna coupling between launchers, assuming the launched and received beams have a Gaussian beam pattern.     

三坐标测量机与FMS集成研究

作为ＦＭＳ质量检测单元的三坐标测量机（ＣＭＭ）多不具备进线功能。如何实现ＣＭＭ与ＦＭＳ集成是目前实施ＦＭＳ．ＣＩＭＳ应用工程的一个重要课题。本文介绍了ＣＭＭ进线技术的具体实施方案。一方面，ＣＭＭ在单元控制器的控制与调度下，实时在线检测工件；另一方面，ＣＭＭ与ＣＡＤ信息交互，实现设计信息与测量信息的双向转换。     

Design and specifications of the diagnostics for the instrumented calorimeter of source for the production of ions of deuterium extracted from radio frequency plasma

In the development of the neutral beam injector for ITER experiment, the test facility SPIDER is going to be built. To measure the beam parameters, several diagnostics are used. One of them is the Short-Time Retractable Instrumented Kalorimeter Experiment (STRIKE) which measures beam uniformity, beamlet divergence, and stripping losses. This contribution gives an overview of the diagnostics dedicated to these measurements: thermal cameras, thermocouples, current sensors, and electrostatic sensors. The specifications of these diagnostics have been defined according to the results of electrostatic and thermal simulations. A failure modes and effects analysis has been performed during the design. Consequently the project of the STRIKE diagnostics has been optimized to reduce the possible failure risks.